Constituent migration model for fast reactor U-Pu-Zr metallic fuel
- 1. Hitachi Ltd. ERL, Ibaraki (Japan)
- 2. Central Research Inst. of Electric Power Industry, Tokyo (Japan)
Description
The metallic fuel behavior of U-Pu-Zr has been actively investigated at Argonne National Laboratory. The Central Research Institute of the Electric Power Industry has been developing a metallic fuel liquid-metal fast breeder reactor concept jointly with several Japanese organizations. One of the development activities resulted in the fuel performance code SESAME. Recently, joint efforts have included the development of more mechanistic models for metallic fuel behavior. One of the models is for the constituent migration behavior in U-Pu-Zr fuels. For a simulation of constituent migration in the Experimental Breeder Reactor 2 (EBR-2) test pins ND30 and ND35, a quasi-binary U-Zr-(11.5 at.% Pu) phase diagram is produced using the U-Pu-Zr ternary phase diagram of O'Boyle and Dwight
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 63
- Series
- Trans. Am. Nucl. Soc.
- Journal Page Range
- 177-178
- ISSN
- 0003-018X
- CODEN
- TANSA
Conference
- Title
- Annual meeting of the American Nuclear Society (ANS).
- Dates
- 2-6 Jun 1991.
- Place
- Orlando, FL (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 23036856
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ALLOY NUCLEAR FUELS; ANL; BINARY ALLOY SYSTEMS; EBR-2 REACTOR; FUEL PINS; LMFBR TYPE REACTORS; PERFORMANCE; PHASE DIAGRAMS; PLUTONIUM; RESEARCH PROGRAMS; RESPONSE FUNCTIONS; SOLUBILITY; TERNARY ALLOY SYSTEMS; URANIUM; ZIRCONIUM
- Descriptors DEC
- ACTINIDES; ALLOY SYSTEMS; BREEDER REACTORS; DIAGRAMS; ELEMENTS; ENERGY SOURCES; EPITHERMAL REACTORS; EXPERIMENTAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FUEL ELEMENTS; FUELS; FUNCTIONS; INFORMATION; LIQUID METAL COOLED REACTORS; MATERIALS; METALS; NATIONAL ORGANIZATIONS; NUCLEAR FUELS; POWER REACTORS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; SODIUM COOLED REACTORS; SOLID FUELS; TRANSITION ELEMENTS; TRANSURANIUM ELEMENTS; US AEC; US DOE; US ERDA; US ORGANIZATIONS
Optional Information
- Secondary number(s)
- CONF-910603--.